Effects of particle fueling and plasma wall interactions on DIII-D discharges

Jackson, G.L.; Baker, D. R.; Holtrop, K.L.; Konoshima, S.; Maingi, R.; Staebler, G. M.; West, W.P.

doi:10.1016/0022-3115(94)00406-4

Cited by 26 publications

(12 citation statements)

References 10 publications

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“…Particle confinement is difficult to measure directly in devices such as DIII-D with a divertor configuration, and a discussion of particle confinement is beyond the scope of this paper. Previous work in DIII-D has shown that the ELM free global particle confinement time is of the same order as the energy confinement time [9,10]. Changes in particle confinement time during ELMing CDH-mode have not yet been measured or calculated.…”

Section: Discussionmentioning

confidence: 99%

Impurity feedback control for enhanced divertor and edge radiation in DIII-D discharges

Jackson¹

1997

Journal of Nuclear Materials

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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark,. manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. : I GA-A22345

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Section: Discussionmentioning

confidence: 99%

Impurity feedback control for enhanced divertor and edge radiation in DIII-D discharges

Jackson¹

1997

Journal of Nuclear Materials

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“…Graphite-based first-wall components have been designed and tested to sustain particle and heat exhausts under steady-state conditions in Tore Supra [9] and DIII-D [10]. HT-7 is a superconducting tokamak [11] with the limiter configuration designed to operate with high power and long-duration discharge.…”

Section: Introductionmentioning

confidence: 99%

The phenomenon of multifaceted asymmetric radiation from the edge with new graphite limiters in Hefei Tokamak-7

Asif

Team²

2007

Plasma Devices and Operations

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A new set of actively cooled toroidal double-ring graphite limiters have been developed in Hefei Tokamak-7 (HT-7) for long-pulse operation. In this paper, the phenomenon of multifaceted asymmetric radiation from the edge (MARFE) has been studied in the ohmic discharges in HT-7. The best correlation has been found between the total input ohmic power and the product of the edge line-averaged density and Z eff . The critical density of the MARFE onset is observed in the region of Z 1/2 eff f GW = 0.9-1.2, where f GW =n e /n GW (heren e is the maximum line-averaged electron density and n GW is the Greenwald density).

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“…The graphite based first wall components have been designed and tested to sustain particle and heat exhausts under steady state conditions in Tore Supra [18].A major part of DIII-D [19] program is focused upon high performance experiments. HT-7 is a superconducting tokamak [20] with the limiter configuration designed to operate with high power and long duration discharge.…”

Section: Introductionmentioning

confidence: 99%

Study of confinement improvement in presence of a MARFE in the HT-7 superconducting tokamak

Asif¹

2006

Braz. J. Phys.

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A new set of actively cooled toroidal double-ring graphite limiters have been developed on the HT-7 tokamk for long pulse operation. In this paper, a Multifaceted asymmetric radiation from the edge (MARFE) phenomena and improved particle confinement induced by a MARFE, characterized by H α line emissions drops and the lineaveraged density increase have been studied in the HT-7 ohmic discharges (where the plasma current I p =145 kA, loop voltage V loop =2-3 V, toroidal field B T =1.7 T, and Z e f f =2-8). It is found that the improved particle confinement phase exists for about 90 ms and the particle confinement time τ P increased about 1.6 times.

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Effects of particle fueling and plasma wall interactions on DIII-D discharges

Abstract: Portions of this document may be illegible in electronic image products. lmages are produced from the best available original. document.

Cited by 26 publications

References 10 publications

Impurity feedback control for enhanced divertor and edge radiation in DIII-D discharges

Impurity feedback control for enhanced divertor and edge radiation in DIII-D discharges

The phenomenon of multifaceted asymmetric radiation from the edge with new graphite limiters in Hefei Tokamak-7

Study of confinement improvement in presence of a MARFE in the HT-7 superconducting tokamak

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